ML19248C746
| ML19248C746 | |
| Person / Time | |
|---|---|
| Site: | 07001193 |
| Issue date: | 03/09/1979 |
| From: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Shelley W KERR-MCGEE CORP. |
| References | |
| NUDOCS 7907050042 | |
| Download: ML19248C746 (2) | |
Text
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AR MCOb UNITED STATES r
J'4 NUCLEAR REGULATORY COMMIFOON y g)fi j f.
WASHINGTON, D. C. 20555 h
?>1AR 0 2 1973 FCRR: CJH
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Docket No. 70-1193 License No. SNM-1174, Amendment No. 3 Kerr-McGee Nut-Corporation ATTN:
Mr. W.
v.
Shelley, Director Regulation and Control Kerr-McGee Center Oklahoma City, Oklahoma 73125 Gentlemen:
In accordance with your application dated November 29, 1978, which superseded in its entirety your application dated December ?, 1977, and pursuant to Title 10, Code of Federal Regulations, Part 70, Special Nuclear Material License No. SNM-1174 is hereby amended to authorize an exception to License Conditions Nos. 21a and 21b to allow the decontamination and dismantling of the obsolete solvent extraction equipment and glove boxes (27A and 278) as described in the Termination Plan--Part III datcd November 28, 1978, and as modified by the additional license conditions listed below.
In additica, in order to conduct the decontamination and dismantling activities authorized by this amendment, an exception to License Conditions Nos. 21a and 21b is also granted to allow the operation of the unnumbered cementing glove box in Room 128, maintenance glove box #45 in Room 116 and slot box T in the General Laboratory (Room 129) as described in the Ternination Plan--Part III, dated November 28, 1978, and as modified by the additional license conditions listed below.
License Conditions:
1.
Precautions shall be taken when using terches or other open flames within plastic " greenhouse" enclosure to assure that flames or hot materials cannot ignite or penetrate the plastic enclosures.
2.
When dismantling chose portions of glove boxes 27A and 27B that can alter differential pressures in other portions of the ventilati'n system, crecautions shall be taken to adjust and restore proper differential pressures and ventilation system ficw rates as scon as pcssible.
285 184 7 907 050 D42 C
Kerr-McGee Nuclear Corporation 3.
The liquid level probe / alarm for the solvent extraction glove box 27A shall be tested at least monthly during the period in which the equipmert and glove box, associated with the solvent extraction operation, are dismantled.
4.
The exemption to the provisions of Section 70.24 of Title 10, Code of Federal Regulations, that was granted under License Condition No.14 to the present license for standby operations, dated July 15, 1977, is deleted during the conduct of activities authorized by this amendment.
5.
Although glove box 27A has been cleaned and it is expected that the plutonium content of any 5 inch diameter, 4.0 liter, poly bottle of hydraulic pump oil or decontamination solution will be very low and should never exceed 40 grams of plutonium, each container renoved from glove box 27A shall be NDA counted before it is placed in the safe storage array, to assure that, for nuclear criticality safety control purposes, it does not contain more than 2.0 kgs. of plutonium.
6.
A maximum of two plutonium-bearing containers, each wi'.h a capacity no larger than 4.0 liters, shall be permitted at the work station where the plutonium content of containers with more than 35 g of plutonium is to be subdivided.
The work station shall be at least two feet from any other plutonium.
All other conditions of Special Nuclear Material License No SNM-1174 shall remain the same.
The Nuclear Regulatory Commission (NRC), Division of Safeguards, will inform ycu by separate correspondence of any safeguards licensing actions taken il conjunction with issuance of this amendment.
In order to permit shipment of the waste generated by the decontamination and dismantling activities authorized by this amendment, an application for an amendment to the Certificate of Compliance No. 6400 (Model No. Super Tiger), or other appropriate packaging, should be submitted to the Chief, Transportation Branch, Division of Fuel Cycle and Material Safety, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555.
FOR THE NUCLEAR REGULATORY CCMMISSION j
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Leland C. Rouse, Acting Chief Fuel Reprccessing and Recycle Branch Division of Fuel Cycle and Material Safety Dated 285 185